CN106710643A - Nuclear reactor core - Google Patents
Nuclear reactor core Download PDFInfo
- Publication number
- CN106710643A CN106710643A CN201510779811.0A CN201510779811A CN106710643A CN 106710643 A CN106710643 A CN 106710643A CN 201510779811 A CN201510779811 A CN 201510779811A CN 106710643 A CN106710643 A CN 106710643A
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- chamber
- core
- reactor
- reactor core
- nuclear
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Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/12—Moderator or core structure; Selection of materials for use as moderator characterised by composition, e.g. the moderator containing additional substances which ensure improved heat resistance of the moderator
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/30—Control of nuclear reaction by displacement of the reactor fuel or fuel elements
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention provides a nuclear reactor core. The nuclear reactor core comprises a reactor core container, a cold chamber, a hot chamber, a core reflector, and a main pump; a reactor core reaction chamber is formed by surrounding of the reactor core container; the cold chamber is arranged on the lower part of the reactor core container, is formed by the bottom and the inner wall of the reactor core container, and is used for accommodating reactor core working medium; the hole chamber is arranged above the cold chamber, and is used for providing an active zone for nuclear fission reaction, and the cross sectional area of the hot chamber is smaller than that of the cold chamber; the core reflector is arranged above the cold chamber, and the side wall of the hot chamber is formed by surrounding of the core reflector; the main pump is used for pumping the reactor core working medium into the hot chamber, so that the liquid level in the hot chamber is higher than that in the cold chamber. The nuclear reactor core is capable of increasing safety of nuclear reactors greatly; reactor operation and accident response are more reliable; and process and equipment needed in reactor trip are simplified.
Description
Technical field
The present invention relates to fission-type reactor technical field, more particularly to a kind of nuclear reactor.
Background technology
In general, the reactive control method overwhelming majority commonly used on nuclear reaction device is to utilize
C＆P systems containing absorbing material, its operation principle is to insert heap when needing and reducing reactor core reactivity
Core, reactivity is reduced to reach, and reactor is reached the purpose of subcritical state.Meanwhile, in light water reactor
In, reactivity is also generally adjusted using boron-containing solution or reduces, as one kind that C＆P systems are controlled
Supplementary means.
The Nuclear Power circle already allows for the intrinsic safety problem and design problem of second generation nuclear reactor, in
The nuclear energy system of a new generation is proposed within 2002 in the forth generation nuclear reactor international symposium that Tokyo is held
System concept, the index that it mainly considers includes environment, the target of economic and security and various aspects：Ensureing
On the premise of economy, safety and reliability is improved, and propose the suggestion of non-passive safety.
Passive safety commonly used in the world at present is substantially based on the non-of Natural Circulation principle
Active residual heat removal system takes the remaining decay heat after reactor emergency shut-down out of, its application principle compared with
It is single, and the response time is slower, it is impossible to directly, nuclear reactivity is rapidly controlled, be a kind of alleviation indirectly
The method of damage sequence.In general, to control and alleviate nuclear power plant accident consequence, it is necessary to use first
The nuclear reactivity of nuclear physics control method reduction reactor core, makes reactor core be in subcritical state and ensure certain
Subcriticality, just can terminate fission reaction and fundamentally control nuclear accident.If by passive principle
Nuclear reactivity control is directly applied to, then can greatly improve reactor shutdown reliability, made inherently safe
Nuclear power station is designed to possibility.
Reactive control device commonly used at present is required for power source, is not belonging to non-passive safety equipment,
The reliability of single equipment is relatively low, the reliability to improve this system, need to improve equipment, control
System, the reliability of power source.
Therefore, designing a kind of introducing negative reactivity that can be passive makes reactor automatically achieve shutdown state
Core critical control unit be very necessary.
The content of the invention
It is a primary object of the present invention to provide a kind of reactor core for fission-type reactor, to significantly improve
The safety and reliability of system, and the setting to active equipment and input are reduced to a certain extent.
Nuclear reactor of the invention is used for nuclear power station fission reactor, and reactor core includes：Reactor core holds
Device, its encirclement forms reactor core reaction chamber；Cold chamber, positioned at core vessel bottom, by core vessel
Bottom and inwall surround to be formed, for accommodating reactor core working medium；Hot chamber, positioned at cold chamber top, it is horizontal
Sectional area is less than cold chamber, and the active region of nuclear fission reaction occurs for providing；Core reflector, is located at
Cold chamber top, its encirclement forms the side wall of hot chamber；Main pump, for reactor core working medium to be pressed into hot chamber
In so that the liquid level in hot chamber is higher than the liquid level in cold chamber.
Reactor core working medium can include liquid molten uranium fluoride and/or thorium fluoride.
Reactor core can also include headroom, and its cross-sectional area is less than cold chamber, for buffering.
Preferably, reactor core also includes cooling device, and it is located at outside core vessel, for carrying out self-heating chamber
And cooled down the reactor core working medium for returning to cold chamber.Cooling device can be heat exchanger in annular.
Reactor core can also include heat release, the remaining decay heat for discharging heap in-core after shutdown.
Alternatively, cold exterior thereto is provided with auxiliary control rod.
Preferably, main pump is located in cold chamber.
Compared with prior art, technology according to the present invention scheme can greatly improve the safety of nuclear reactor
Property, more reliable when making reactor operation and incident response, flow and equipment needed for simplifying shutdown, with
The card rod that solve the problems, such as current nuclear reactor and may occur when carrying out shutdown using C＆P systems, Ke Yizuo
It is the secondary shutdown system of C＆P systems, to meet, the shutdown mode during reactor is designed is multifarious to be wanted
Ask.
Brief description of the drawings
Accompanying drawing described herein is used for providing a further understanding of the present invention, constitutes of the application
Point, schematic description and description of the invention is used to explain the present invention, does not constitute to of the invention
Improper restriction.In the accompanying drawings：
Fig. 1 is the structural representation of nuclear reactor according to embodiments of the present invention；
Fig. 2 is the structural representation of reactor core according to the preferred embodiment of the invention.
In the drawings, same or analogous part is represented using identical reference number.
Specific embodiment
It is below in conjunction with accompanying drawing and specifically real to make the object, technical solutions and advantages of the present invention clearer
Example is applied, the present invention is described in further detail.
In the following description, to " one embodiment ", " embodiment ", " example ", " example " etc.
Reference show the embodiment or example of such description can include special characteristic, structure, characteristic, property,
Element or limit, but not each embodiment or example necessarily include special characteristic, structure, characteristic,
Property, element or limit.In addition, reusing phrase " in one embodiment " although it is possible to refer to
For identical embodiment, but it is not necessarily referring to identical embodiment.
For the sake of simplicity, eliminated well known to a person skilled in the art some technical characteristics in below describing.
Fig. 1 shows the reactor core 100 for nuclear power station fission reactor according to embodiments of the present invention.
Reactor core 100 mainly includes core vessel 110, cold chamber 120, hot chamber 130, core reflector
140 and main pump 150.
Core vessel 110 is surrounded and forms reactor core reaction chamber.
Cold chamber 120 is located at the bottom of core vessel 110, is surrounded by the bottom of core vessel 110 and inwall
Formed, for accommodating reactor core working medium.Reactor core working medium can include liquid molten uranium fluoride and/or thorium fluoride.
Alternatively, it is provided with auxiliary control rod outside cold chamber 120.
Hot chamber 130 is located at the top of cold chamber 120, and its cross-sectional area is less than cold chamber 120, for carrying
For the active region that nuclear fission reaction occurs.
Core reflector 140 is located at the top of cold chamber 120, and its encirclement forms the side wall of hot chamber 130.
Main pump 150 is used to be pressed into reactor core working medium in hot chamber 130 so that the liquid level in hot chamber 130
Higher than the liquid level in cold chamber 120.Preferably, main pump 150 is located in cold chamber 120.
Reactor core 100 can also include headroom, and its cross-sectional area is less than cold chamber 120, for buffering.
In order to carrying out self-heating chamber 130 and cooling down the reactor core working medium for returning to cold chamber 120, preferably
Ground, reactor core 100 also includes cooling device, and it is located at outside core vessel 110.Cooling device can be ring
Heat exchanger in shape.
In order to discharge the remaining decay heat of heap in-core after shutdown, reactor core 100 can also include heat release.
Fig. 2 shows reactor core according to the preferred embodiment of the invention.
It is fuel and cooling agent that reactor core uses liquid molten uranium fluoride (or thorium).This is a kind of liquid
, mainly (there is controllable holding including hot chamber 1 in structure in the non-passive safety reactor core of position control reactivity
The active region of continuous nuclear fission reaction), cold chamber 2, reactor vessel 3, core reflector 4, main pump 5,
The other equipment in top cushion space 6, heat exchanger 7 and secondary circuit.Meanwhile, it is anti-after shutdown in order to ensure
The long-term safety of heap is answered, necessary passive residual heat removal should be also set in upper chamber and lower chamber
System is used to derive the remaining decay heat in reactor after shutdown.
Fuel/cooling agent working medium in hot chamber 1 and cold chamber 2 is all accommodate by reactor vessel 3,
The utilization rate that core reflector 4 ensures the free neutron for maintaining nuclear fission reaction is set simultaneously.Reactor core reflects
4 reflection direction radial inward of layer, it is illustrated that its thickness is δ, its encirclement forms cylindric hot chamber 1,
The height of hot chamber 1 is illustrated for h, the radius of hot chamber 1 are r.When normal reactor operation, hot chamber
Core critical condition is reached full of the working medium provided by main pump 5 in 1, so that it is anti-that lasting nuclear fission occurs
Should, maintenance work state.Working medium liquid level is higher than working medium liquid level in cold chamber 2 in hot chamber 1, it is illustrated that
Difference in height is D.Working medium after heating returns to cold chamber 2 after heat exchanger 7 is cooled down and completes a flowing
Circulation.When reactor occurs abnormal conditions, main pump 5 is powered and hinders power-off, hot chamber 1 and cold chamber for some reason
Pressure head that liquid level difference D between room 2 because lose is provided by main pump 5 and reduce rapidly, hot chamber 1 is lived
Property area in nuclear fuel reduce and make the automatic shutdown of reactor (automatic during shutdown liquid level shown in dotted line less than in figure
Shutdown), the power of reactor core is reduced to the state of shutdown soon, and reactor residual heating is by heat exchanger 7
Or other accidents emergency service is taken away.Top cushion space 6 is mainly used to alleviate pressure oscillation during operation
And change.
In addition, part-structure of the invention can variation, can such as use in annular heat exchanger to improve heat exchange
Efficiency；Also the main pump of internal immersion can be used to improve the pressure head of pump；Outside in lower chambers sets auxiliary
Control rod is helped to provide diversity shutdown mode etc..
Operation principle of the invention is：In the case of using liquid or ball bed reactor core, using normal operation
When the liquid level difference that produces of main pump pressure head, the active region of chain reaction is arranged on the top of reactor core.Work as generation
When dead electricity accident or main pump failure are stopped transport, liquid level is less than active region because pressure head is lost highly, makes chain type
Reaction is automatically stopped, and reaches the state of passive shutdown.
The beneficial effects of the invention are as follows：
First, the present invention realizes the passive automatic safe shutdown in the case of dead electricity or main pump failure.
During normal operation, liquid fuel is squeezed into active region positioned at reactor core top using the pressure head of main pump, it is real
Existing chain fission nuclear reaction.When the accident of main pump power is lost, the liquid level of active region is due to losing
The pressure head of main pump is removed and has declined, liquid fuel has completely or partially entered lower chamber, lower chamber periphery
There is no reflecting layer and internal capacity is not reached and closes on size, chain fission nuclear reaction stops immediately, well
Realize the passive shutdown of reactor, it is ensured that the reliability of shutdown safety.Can be with traditional control rod
Shut-down method complements each other application, for reactor shutdown diversity provides new selection from shutdown principle
Approach.
2nd, the present invention is connected nuclear reactivity and liquid level position by the setting of upper and lower part chamber,
Reactivity control is further simplified, the design built in heap also simplify on the basis of reliability is improved,
The key equipment of core region and the number of components are reduced, more heat transmission equipments or function passage can be set,
More effectively make use of space in heap.
3rd, the liquid molten fluoride fuel and cooling agent strong adaptability that the present invention is used, can make full use of
Various fissile nuclides such as uranium, thorium, or even can be using the nuclear fuel of pebble bed reactor, you can use fast reactor pattern
Operation, can also use thermal reactor mode operation, according to the mode operation of fast reactor, can the various heap-type of transmuting
Spentnuclear fuel.
4th, room for improvement is provided for the capital equipments such as main reactor pump simplify design, using feelings of the invention
Under condition, main pump is not required to install the device of the extension blade coasting time of large volume, will effectively reduce main pump peace
Dress volume, for in-pile component installation, improve efficiency advantage is provided.
Embodiments of the invention are the foregoing is only, is not intended to limit the invention, for this area
Technical staff for, the present invention can have various modifications and variations.It is all in the spirit and principles in the present invention
Within, any modification, equivalent substitution and improvements made etc. should be included in claim of the invention
Within the scope of.
Claims (8)
1. a kind of nuclear reactor, for nuclear power station fission reactor, it is characterised in that including：
Core vessel, its encirclement forms reactor core reaction chamber；
Cold chamber, positioned at the core vessel bottom, shape is surrounded by the bottom of the core vessel and inwall
Into for accommodating reactor core working medium；
Hot chamber, positioned at the cold chamber top, its cross-sectional area is less than the cold chamber, for providing
There is the active region of nuclear fission reaction；
Core reflector, positioned at the cold chamber top, its encirclement forms the side wall of the hot chamber；
Main pump, for reactor core working medium to be pressed into the hot chamber so that the liquid level in the hot chamber is high
Liquid level in the cold chamber.
2. nuclear reactor according to claim 1, it is characterised in that the reactor core working medium
Including liquid molten uranium fluoride and/or thorium fluoride.
3. nuclear reactor according to claim 1, it is characterised in that also empty including top
Between, its cross-sectional area is less than the cold chamber, for buffering.
4. nuclear reactor according to claim 1, it is characterised in that also filled including cooling
Put, it is located at outside the core vessel, for from the hot chamber and the cold chamber will be returned
Reactor core working medium is cooled down.
5. nuclear reactor according to claim 4, it is characterised in that the cooling device
It is heat exchanger in annular.
6. nuclear reactor according to claim 1, it is characterised in that also filled including heat extraction
Put, the remaining decay heat for discharging heap in-core after shutdown.
7. nuclear reactor according to claim 1, it is characterised in that outside the cold chamber
Portion is provided with auxiliary control rod.
8. nuclear reactor according to claim 1, it is characterised in that the main pump is located at
In the cold chamber.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201510779811.0A CN106710643B (en) | 2015-11-13 | 2015-11-13 | Nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201510779811.0A CN106710643B (en) | 2015-11-13 | 2015-11-13 | Nuclear reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN106710643A true CN106710643A (en) | 2017-05-24 |
| CN106710643B CN106710643B (en) | 2018-08-14 |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201510779811.0A Expired - Fee Related CN106710643B (en) | 2015-11-13 | 2015-11-13 | Nuclear reactor |
Country Status (1)
| Country | Link |
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| CN (1) | CN106710643B (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107369479A (en) * | 2017-07-31 | 2017-11-21 | 清华大学天津高端装备研究院 | The passive reactor shut-off system and nuclear reactor based on pressure difference for integrated heap |
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| CN102782768A (en) * | 2010-04-21 | 2012-11-14 | 株式会社东芝 | Liquid metal cooled reactor and heat removal method for same |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107369479A (en) * | 2017-07-31 | 2017-11-21 | 清华大学天津高端装备研究院 | The passive reactor shut-off system and nuclear reactor based on pressure difference for integrated heap |
| CN107369479B (en) * | 2017-07-31 | 2023-08-22 | 清华大学天津高端装备研究院 | Differential pressure-based passive shutdown system for an integrated stack and a nuclear reactor |
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| Publication number | Publication date |
|---|---|
| CN106710643B (en) | 2018-08-14 |
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